Authors & Affiliations
Dekusar V.M., Moseev A.L., Moseev P.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Dekusar V.M. – Head of Laboratory, Cand. Sci. (Tech.), A.I. Leypunsky Institute for Physics and Power Engineering.
Moseev P.A. – Junior Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
This paper presents a brief review of the capabilities of the CYCLE code. The code allows simulation of key facilities of the external fuel cycle, thermal and fast nuclear reactors. As an important feature, the CYCLE code allows the evolution of the fuel’s nuclide composition both in reactors and at the external fuel cycle phase to be considered in details. The aim is to determine the characteristics of the fuel cycle based on VVER-TOI and BN-1200 reactors with fuel of different composition. Characteristics of reactor systems with spent fuel reprocessing and recycling of plutonium are compared to those of the reference system consisting only of VVER-TOI with uranium oxide fuel, operating in an open fuel cycle. The analysis was made of a model scenario to transfer the two-component nuclear power system that consists of thermal reactors of the VVER-TOI type and fast reactors BN-1200 type to the equilibrium mode with full spent nuclear fuel reprocessing and complete recycling of separated plutonium. The specific logistics was developed to use plutonium of various isotopic compositions in the system of fast and thermal reactors. The results of computational fuel cycle simulation are presented for the two-component nuclear power system considered.
simulation, modeling, scenario, nuclear fuel cycle, fast reactor, thermal reactor, recycling, depleted uranium, plutonium composition, plutonium equivalenting, plutonium store, fuel characteristics
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